ENTRY 14531 20190417 14511453100000001 SUBENT 14531001 20190417 14511453100100001 BIB 11 29 1453100100002 TITLE Tritium yield in the thermal neutron fission of 233U 1453100100003 AUTHOR (D.L.Horrocks,E.B.White) 1453100100004 INSTITUTE (1USAANL) 1453100100005 REFERENCE (J,NP/A,151,65,1970) 1453100100006 #doi:10.1016/0375-9474(70)90967-X 1453100100007 #NSR: 1970HO20 1453100100008 FACILITY (REAC,1USAANL) The Argonne CP-5 reactor thermal isotope1453100100009 tray. 1453100100010 INC-SOURCE (REAC) The flux was between 3.5E+12 n/cm**2/sec and 1453100100011 4.5E+12 n/cm**2/sec. 1453100100012 DETECTOR (SCIN) The final volume of the purified tritiated water1453100100013 was measured to determine the recovery yield 1453100100014 (essentially always 100%) of the aqueous added to the 1453100100015 samples as HNO3 and NaOH solutions. 1453100100016 Aliquotes of this water were counted in a coincidence 1453100100017 type liquid scintillation counter. Using a dioxane 1453100100018 base scintillas, or solution with 2 ml of the water in 1453100100019 15 ml of the dioxane solution the counting efficiency 1453100100020 for tritium was 11%. Changes in the counting efficiency1453100100021 due to quenching by impurities in the sample and/or 1453100100022 decomposition of the dioxane were monitored by the 1453100100023 Compton edge technique. 1453100100024 METHOD (CHSEP) 1453100100025 MONITOR (92-U-233(N,F)56-BA-140,CUM,FY,,MXW) The number of 1453100100026 fissions was determined from an analysis of the 140Ba 1453100100027 produced during the irradiation and the 6.0% fission 1453100100028 yield of 140Ba from the thermal fission of 233U. 1453100100029 MONIT-REF ((MONIT),,J,NUC,16,78,1958) 1453100100030 HISTORY (20190416C) OG. 1453100100031 ENDBIB 29 0 1453100100032 COMMON 2 3 1453100100033 EN-DUMMY MONIT 1453100100034 EV PC/FIS 1453100100035 2.5300E-02 6. 1453100100036 ENDCOMMON 3 0 1453100100037 ENDSUBENT 36 0 1453100199999 SUBENT 14531002 20190417 14511453100200001 BIB 5 29 1453100200002 REACTION (92-U-233(N,F)1-H-3,TER,FY,,MXW) 1453100200003 SAMPLE A few tenths of a gram of 233U308 were purified 1453100200004 (especially from lithium) by dissolution in HNO3, 1453100200005 ether extraction, back-extraction into water and 1453100200006 re-ignition to 233U308. The isotopic composition of 1453100200007 this sample: 1453100200008 (92-U-233,ENR=0.9687)+-0.0003 1453100200009 (92-U-234,ENR=0.0122)+-0.0002 1453100200010 (92-U-235,ENR=0.00196)+-0.00004 1453100200011 (92-U-236,ENR=0.000019)+-0.000001 1453100200012 (92-U-238,ENR=0.0171)+-0.0002. 1453100200013 The 233U3O8 ether extractions and the use of platinum 1453100200014 metal irradiation capsules removed the possibility of 1453100200015 tritium contamination from the sample and the sample 1453100200016 container. 1453100200017 Several grams of 238U3O8 were also purified by ether 1453100200018 extraction cycles. This sample was 99.983 atom% 238U 1453100200019 and only 0.017 atom% 235U. This depleted U3O8 was mixed1453100200020 with the 233U308 to give a weight ratio of 238U to 233U1453100200021 of approximately 10:1. 1453100200022 Samples of 0.5 to 1.5g of the 10:1 238,233U308 were 1453100200023 weighed into platinum irradiation capsules which were 1453100200024 sealed to prevent any gas leaks. These were then 1453100200025 irradiated. 1453100200026 ERR-ANALYS (DATA-ERR) No information 1453100200027 STATUS (TABLE) Data taken from the table 1 of 1453100200028 Nucl.Phys.A,151,65,1970. 1453100200029 COMMENT Compiler's comment: Author's units "Fissions / T atom"1453100200030 were converted by compiler to %/fission (PC/FIS). 1453100200031 ENDBIB 29 0 1453100200032 NOCOMMON 0 0 1453100200033 DATA 2 1 1453100200034 DATA DATA-ERR 1453100200035 PC/FIS PC/FIS 1453100200036 9.0909E-03 0.5785E-03 1453100200037 ENDDATA 3 0 1453100200038 ENDSUBENT 37 0 1453100299999 SUBENT 14531003 20190417 14511453100300001 BIB 5 15 1453100300002 REACTION (94-PU-239(N,F)1-H-3,TER,FY,,MXW) 1453100300003 SAMPLE Of the six PuO2 samples measured three gave values near1453100300004 that which could be expected from the Z2/A dependency. 1453100300005 The experimental values obtained on these three samples1453100300006 are presented. The other three values indicated lower 1453100300007 tritium yields. A big differences between the values 1453100300008 and a large error were because of the difficulty of 1453100300009 dissolving the PuO2 after it has been in the reactor. 1453100300010 FLAG (1.) First sample 1453100300011 (2.) Second sample 1453100300012 (3.) Third sample 1453100300013 STATUS (TABLE) Data taken from the text of 1453100300014 Nucl.Phys.A,151,65,1970. 1453100300015 COMMENT Compiler's comment: Author's units "Fissions/T atom" 1453100300016 were converted by compiler to %/fission (PC/FIS). 1453100300017 ENDBIB 15 0 1453100300018 NOCOMMON 0 0 1453100300019 DATA 2 3 1453100300020 DATA FLAG 1453100300021 PC/FIS NO-DIM 1453100300022 1.8182E-02 1. 1453100300023 2.5000E-02 2. 1453100300024 5.0000E-02 3. 1453100300025 ENDDATA 5 0 1453100300026 ENDSUBENT 25 0 1453100399999 ENDENTRY 3 0 1453199999999